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Temperature Prediction for the Sirius-2c Nuclear Propulsion Fuel Experiment Conducted at the TREAT Facility.

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Title: Temperature Prediction for the Sirius-2c Nuclear Propulsion Fuel Experiment Conducted at the TREAT Facility.
Authors: Jaradat, Mustafa K.1 (AUTHOR) Mustafa.Jaradat@inl.gov, Schunert, Sebastian2 (AUTHOR), Gleicher, Frederick N.1 (AUTHOR), DeHart, Mark1 (AUTHOR)
Source: Nuclear Science & Engineering. 2026 Suppl 1, Vol. 200, pS253-S269. 17p.
Subject Terms: *Control elements (Nuclear reactors), *Temperature measurements, *Nuclear facilities, *Nuclear reactors
Company/Entity: United States. National Aeronautics & Space Administration
Abstract: This study presents a predictive transient model developed for simulating experiments at the Transient Reactor Test (TREAT) Facility and its application to the Sirius-2c experiments. We introduce an innovative approach to predict control rod motion, reactor power, and specimen temperature during transient experiments using Griffin, BISON, and the stochastic tool packages of the Multiphysics Object-Oriented Simulation Environment. The model provides a blind prediction of the specimen temperature evolution during transient tests given a desired power signal. Initially, our model accurately predicts the transient motion of the control rods to achieve the desired reactor power profile. Subsequently, it predicts the specimen temperature based on the power deposited within the specimen. The simulation results show strong agreement with the measured reactor power and control rod positions; however, the specimen temperature is slightly overpredicted, primarily because of assumptions about surface emissivities. When considering a more accurate set of specimen emissivities, the predicted temperature aligns exceptionally well with the measured values according to post-analysis results. The simulation results will support the design and analysis of the National Aeronautics and Space Administration sponsored Sirius series of experiments for nuclear thermal propulsion applications, and the model can be utilized to assist in the design and optimization of new experiments to be conducted at the TREAT Facility. [ABSTRACT FROM AUTHOR]
Database: Energy & Power Source
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  Availability: 0
Header DbId: enr
DbLabel: Energy & Power Source
An: 192155899
AccessLevel: 6
PubType: Academic Journal
PubTypeId: academicJournal
PreciseRelevancyScore: 0
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  Data: Temperature Prediction for the Sirius-2c Nuclear Propulsion Fuel Experiment Conducted at the TREAT Facility.
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  Data: <searchLink fieldCode="JN" term="%22Nuclear+Science+%26+Engineering%22">Nuclear Science & Engineering</searchLink>. 2026 Suppl 1, Vol. 200, pS253-S269. 17p.
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  Data: *<searchLink fieldCode="DE" term="%22Control+elements+%28Nuclear+reactors%29%22">Control elements (Nuclear reactors)</searchLink><br />*<searchLink fieldCode="DE" term="%22Temperature+measurements%22">Temperature measurements</searchLink><br />*<searchLink fieldCode="DE" term="%22Nuclear+facilities%22">Nuclear facilities</searchLink><br />*<searchLink fieldCode="DE" term="%22Nuclear+reactors%22">Nuclear reactors</searchLink>
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  Data: <searchLink fieldCode="DE" term="%22United+States%2E+National+Aeronautics+%26+Space+Administration%22">United States. National Aeronautics & Space Administration</searchLink>
– Name: Abstract
  Label: Abstract
  Group: Ab
  Data: This study presents a predictive transient model developed for simulating experiments at the Transient Reactor Test (TREAT) Facility and its application to the Sirius-2c experiments. We introduce an innovative approach to predict control rod motion, reactor power, and specimen temperature during transient experiments using Griffin, BISON, and the stochastic tool packages of the Multiphysics Object-Oriented Simulation Environment. The model provides a blind prediction of the specimen temperature evolution during transient tests given a desired power signal. Initially, our model accurately predicts the transient motion of the control rods to achieve the desired reactor power profile. Subsequently, it predicts the specimen temperature based on the power deposited within the specimen. The simulation results show strong agreement with the measured reactor power and control rod positions; however, the specimen temperature is slightly overpredicted, primarily because of assumptions about surface emissivities. When considering a more accurate set of specimen emissivities, the predicted temperature aligns exceptionally well with the measured values according to post-analysis results. The simulation results will support the design and analysis of the National Aeronautics and Space Administration sponsored Sirius series of experiments for nuclear thermal propulsion applications, and the model can be utilized to assist in the design and optimization of new experiments to be conducted at the TREAT Facility. [ABSTRACT FROM AUTHOR]
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RecordInfo BibRecord:
  BibEntity:
    Identifiers:
      – Type: doi
        Value: 10.1080/00295639.2024.2445470
    Languages:
      – Code: eng
        Text: English
    PhysicalDescription:
      Pagination:
        PageCount: 17
        StartPage: S253
    Subjects:
      – SubjectFull: Control elements (Nuclear reactors)
        Type: general
      – SubjectFull: Temperature measurements
        Type: general
      – SubjectFull: Nuclear facilities
        Type: general
      – SubjectFull: Nuclear reactors
        Type: general
      – SubjectFull: United States. National Aeronautics & Space Administration
        Type: general
    Titles:
      – TitleFull: Temperature Prediction for the Sirius-2c Nuclear Propulsion Fuel Experiment Conducted at the TREAT Facility.
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            NameFull: Jaradat, Mustafa K.
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            NameFull: Schunert, Sebastian
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            NameFull: Gleicher, Frederick N.
      – PersonEntity:
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            NameFull: DeHart, Mark
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          Dates:
            – D: 02
              M: 02
              Text: 2026 Suppl 1
              Type: published
              Y: 2026
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            – Type: issn-print
              Value: 00295639
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              Value: 200
          Titles:
            – TitleFull: Nuclear Science & Engineering
              Type: main
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